Gamma-ray and neutron shielding features for some fast neutron moderators of interest in Cf-based boron neutron capture therapy.

Monte Carlo simulations (MCNP) were carried out to model suitable Cf-based gamma transmission and neutron attenuation geometries to evaluate the gamma-ray shielding features and neutron attenuation capabilities for AlO, MgF, Fluental and AlF, as fast neutron moderators of potential interest in Cf-based Born Neutron Capture Therapy (BNCT) facilities. The mass attenuation coefficient (μ/ρ), Half-Value Layer (HVL), Mean Free Path (MFP) and gamma transmission factor (I/I) for AlO, MgF, Fluental and AlF were simulated at gamma energies, 0.3 MeV, 0.364 MeV, 0.662 MeV, 1.25 MeV and 7.12 MeV. The MCNP simulated μ/ρ values were compared to theoretical XCOM values and good agreement was observed. The ratio of total thermal neutron flux to the total fast neutron flux (φ /φ ) and the total flux of gamma rays (φ ) resulting from thermal neutron capture (n,γ) reactions, were simulated and compared as a function of thickness for the four sample moderators. The values of the effective fast neutron removal cross section Σ (cm) for the four sample moderators were calculated and compared.